摘要
本文介绍了在临界装置上进行堆芯温度系数测量的方法、测量仪器、实验结果及校核计算结果。实验结果表明,温度系数均为负值,满足反应堆设计的安全要求;实验结果与校核计算结果相符,验证了堆芯核设计程序的可靠性。
The paper introduces the measurement methods,instruments,experimental results and calculation results of temperature coefficient of the core in the critieal facility.The experimental results show that measurement values of temperature coefficient are all negative,which satisfy the safety requirement for the design of reactors.The experimental results are eorrespondent to calculation results of temperature coefficient of the core,which verifies the reliability of core design codes .
作者
黄礼渊
代启东
牛江
阳林锋
HUANG Li-yuan;DAI Qi-dong;NIU Jiang;YANG Lin-feng(Reactor Engineering Research Division,Nuclear Power Institute of China,Chengdu 610213,China)
出处
《核电子学与探测技术》
CAS
北大核心
2018年第5期645-648,共4页
Nuclear Electronics & Detection Technology
关键词
临界装置
温度系数
反应性
温度
critical facility
temperature coefficient
reactivity
temperature